ML20133N948

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Safety Evaluation Supporting Amend 101 to License DPR-65
ML20133N948
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/02/1985
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20133N940 List:
References
TAC-57423, TAC-57424, TAC-57425, TAC-57426, TAC-57427, NUDOCS 8508140068
Download: ML20133N948 (3)


Text

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'4 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.101T0 DPR-65 NORTHEAST NUCLEAR ENERGY COMPANY, ET AL, MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 DOCKET N0. 50-336 INTRODUCTION

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By letters dated March 28, March 29 (3), and April 4, 1985, Northeast Nuclear Energy Company (NNECO or licensee) proposed five changes to the Millstone Nuclear Power Station, Unit 2, Technical Specifications. The first change would revise Technical Specification 3.7.5 entitled ': Flood Level" to delete a reference to a Station Emergency Procedure and to make minor changes in wording.

The second change would revise Technical Specification sections 4.4.5.1.3, 3.4.6.2 and Table 4.7-2 to delete specific footnotes for Cycle 5 refueling and operations.

The third change would revise Technical Specification Table 3.3-6 entitled

" Radiation Monitoring Instrumentation." The current Technical Specification requires containment atmosphere particulate and gaseous radiation monitors to be operable in all modes. The proposed modification adds a footnote to delete the requirement for these radiation monitors to be in operation during Type "A" integrated leak rate testing.

The fourth change would revise Technical Specification surveillance requirement 4.8.1.1.2.c.5.d to make Diesel Generator Testing consistent with requirements of NRC Generic Letter 83-30.

The fifth change would revise Technical Specification surveillance requirement 4.5.2.c.3 for ECCS subsystems. This is a wording change which deletes the physical description of trisodium phosphate dodecahydrate.

Evaluation The first change is to make Technical Specification 3.7.5 flood level consis-tent with other technical specifications by deleting the reference to a station procedure. Other minor wording changes are made for clarity.

The second change deletes Cycle 5 specific footnotes. These footnotes no longer apply to Millstone Unit 2 which has completed Cycle 6.

This proposed deletion is administrative and will add clarity to the applicable portions of the Technical Specifications.

8508140068 850802 PDR ADOCK 05000336 p

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i i The third change would allow removing from service the containment atmosphere particulate and gaseous radiation monitors during Type "A" integrated leak rate testing. The purpose of the Type "A" integrated leak rate test is to verify the leak-tight integrity of the primary reactor containment..This test is performed with the reactor in cold shutdown, Mode 5.

The Standard Technical Specifications for Combustion Engineering PWRs does not require the containment atmosphere radiation monitors to be operable in Mode 5.

The fourth change deletes surveillance requirement 4.8.1.1.2.c.5.d from diesel generator testing. The current surveillance requires, " Verifying that on a simulated loss of the diesel generator [with offsite power not available], the loads are shed from the emergency busses, the emergency busses are reenergized with permanently connected through the load sequencer, and the diesel operates for > 5 minutes while its generator is loaded with the emergency loads". This change is consistent with Generic Letter 83-30 which states that this require-ment is in excess of the scope of GDC 17.

The fifth change is a revision to the wording of surveillance requirement 4.5.2.c.3 for ECCS subsystems. The current surveillance requires " Verifying that a minimum total of 110 cubic feet of solid granular trisodium phosphate dodecahydrate (TPS) is contained with the storage baskets". The proposed modification deletes the words " solid" and " granular" to prevent possible misinterpretation of the physical description of TPS. TPS has the tendency to cake together making large clumps. However, surveillance 4.5.2.c.4 verifies the ability of a representative sample of TPS to raise the pH of borated water.

This is required to be done without agitation. Deleting the words " solid" and

" granular" from surveillance requirement 4.5.2.c.3 would preclude replacing the

.TPS in the storage baskets due to caking without affecting its functional requirements.

The staff has evaluated the proposed changes to the Technical Specifications and concludes that these changes are administrative and do not involve any physical change to the plant's safety-related structures, systems or compon-ents. Further, these changes do not increase the likelihood of a malfunction of safety-related equipment, or increase the consequences of a accident previously analyzed or create the possibility of a malfunction different from those previously evaluated. Therefore, based on the above, the staff finds the proposed changes to the Technical Specifications to be acceptable.

Environmental Consideration This amendment involves changes in recordkeeping, reporting or administrative procedures or requirements. The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR i

51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance i

of this amendment.

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. Conclusion The staff has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.

Date: August 2, 1985 Principal Contributor:

J. Robertson, RI 9+-

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